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US3162577A - Reactor control with thorium control grid - Google Patents

Reactor control with thorium control grid Download PDF

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US3162577A
US3162577A US321984A US32198463A US3162577A US 3162577 A US3162577 A US 3162577A US 321984 A US321984 A US 321984A US 32198463 A US32198463 A US 32198463A US 3162577 A US3162577 A US 3162577A
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reactor
core
thorium
control grid
control
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William C Redman
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    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C1/00—Reactor types
    • G21C1/04—Thermal reactors ; Epithermal reactors
    • G21C1/06—Heterogeneous reactors, i.e. in which fuel and moderator are separated
    • G21C1/14—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor
    • G21C1/16—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor moderator and coolant being different or separated, e.g. sodium-graphite reactor, sodium-heavy water reactor or organic coolant-heavy water reactor
    • G21C1/18—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor moderator and coolant being different or separated, e.g. sodium-graphite reactor, sodium-heavy water reactor or organic coolant-heavy water reactor coolant being pressurised
    • G21C1/20—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor moderator and coolant being different or separated, e.g. sodium-graphite reactor, sodium-heavy water reactor or organic coolant-heavy water reactor coolant being pressurised moderator being liquid, e.g. pressure-tube reactor
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C7/00—Control of nuclear reaction
    • G21C7/06—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section
    • G21C7/08—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section by displacement of solid control elements, e.g. control rods
    • G21C7/10—Construction of control elements
    • G21C7/113—Control elements made of flat elements; Control elements having cruciform cross-section
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C7/00—Control of nuclear reaction
    • G21C7/06—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section
    • G21C7/08—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section by displacement of solid control elements, e.g. control rods
    • G21C7/10—Construction of control elements
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors

Definitions

  • This invention relates to a nuclear reactor and particularly to a urania-thoria power reactor wherein heavy water serves as moderator.
  • the invention also relates to novel means for controlling such a reactor to enhance the neutron economy and extend the useful life of the reactor.
  • the invention further relates to a method of operating such a reactor.
  • Power reactors are always constructed with an appreciable excess reactivity to extend the lifetime .of the reactor. It is customary to use burnable poisons or shim control rods to compensate for this initial excess reactivity. As the fuel in the reactor burns out, the burnable poison burns out and/ or the shim rods are withdrawn to increase the available reactivity. Both of these expedients succeed in extending the reactivity lifetime of a reactor but both adversely affect the neutron economy in the reactor due to nonproductive loss of neutrons in the burnable poison and the shim rods.
  • the thoria-urania system is very attractive for power reactors because of the abundance ofthoria, the high burnup potentially attainable in a thoria-urania reactor, and the compatibility of thoria and urania with hightemperature water.
  • heavy water is attractive as a moderator in a thoria-urania reactor because of the good neutron economy attainable therewith.
  • neutron economy is impaired significantly by the large capture cross section of 27-day Pa which is an intermediate product in the transmutation of Th to U as shown by the following nuclear equations:
  • Th +n Th +'y 233 2s3+ 233 233+ It is accordingly an object of the present invention to develop a nuclear reactor having improved neutron economy and increased core lifetime.
  • a urania-thoria reactor which is approximately twice the height required by nuclear design considerations and which includes a movable control grid of thorium slightly greater than one-half the height of the reactor.
  • the control grid is employed for ordinary control of the reactor, thereby enhancing the neutron economy of the reactor since a useful product is formed in the control grid.
  • the control grid also makes it possible to mitigate the effect of Pa on the neutron economy of the reactor.
  • FIG. 1 is a diagrammatic cross-section of a nuclear reactor illustrating the present invention
  • FIG. 2 is a horizontal cross-section thereof taken on the line 22,
  • FIG. 3 is a perspective view of a control grid which is of primary importance to the present invention.
  • FIG. 4 is a horizontal cross-section of a typical fuel element.
  • the reactor comprises a core 1 0 and a reflector 11 surrounding the core.
  • Core 10 and reflector 11 are separated by an inner shell 12 while an outer shell 13 encloses the entire reactor.
  • Reflector 11 extends the full length of the core between an upper plate 14 at the top of inner shell 12 and a lower plate 15 at the bottom of inner shell 12 and light water is introduced thereinto through inlet 16 and withdrawn through outlet 17.
  • Core 10 is composed of bundles of parallel fuel rods 18 (see FIG. 4) disposed in a plurality of vertical pressure tubes 19. Spiral wires 20 on the fuel rods 18 assure that the fuel rods are properly spaced. Fuel rods 18 are supported by clamps (notshown) at the top and bottom of the pressure tubes 19.
  • Pressure tubes 19 extend between a lower support grid 21 disposed at the bottom of inner shell 12 and an upper guide grid 22 disposed intermediate of inner shell 12 and above the top of core 10.
  • An annular inlet header 23 is disposed below the core while an annular outlet header 24 is disposed above the core.
  • Lower pressure tube extensions 25 and inlet ducts 26 provide communication between inlet header 23 and pressure tubes 19 while upper pressure tube extensions 27 and outlet ducts 28 provide communication. between outlet header 24 and pressure tubes 19.
  • Fuel rods 18 consist of fired pellets of a uniform mix- 1 ture of highly enriched urania and thoria in a tube formed I of a corrosion-resistant material of low neutron capture cross-section such as Ziroaloy-II.
  • the primary coolant flow through the reactor passes through pressure tubes 19. Heavy water under pressure enters pressure tubes 19 from ducts 26 and header 23 and is there heated by fuel rods 18. The heated heavy water is withdrawn through outlet ducts 28 and outlet header 24 to produce power exterior to the reactor.'
  • Inner shell 12 contains a body of heavy Water 29 which serves asmoderator and secondary coolant.
  • a continuous flow of heavy water is maintained by introducing heavy water into reactor vessel 13 below the core through moderator inlet 3d and withdrawing it from reactor vessel 13 above the core through moderator outlet 31.
  • the heavy water passes into and out of inner shell 12 through perforations 32 (see FIG. 2) in support grid 21 and guide grid 22.
  • control grid 33 comprises an outer box55 which is open at both ends and intersecting sheets 36 of thorium in the box 35.
  • the sheets of thorium are spaced far enough apart to clear pressure tubes 19 so that the control grid 33 interpenetrates the reactor core 10.
  • the thorium employed to form control grid 33 is, of course, clad in a corrosionresistant material such as Zircaloy-II.
  • control plates 37 operated by cables 38 are provided for safety control.
  • the primary point of novelty according to the present invention resides in the use of a control grid 33 of slightly greater than one-half the height of the core in a reactor core'which is twice the height required by design considerations for criticality. Thus only half of the core is required for operation of the reactor.
  • the thorium grid is placed so as to prevent a chain reaction in either the top half or the bottom half ofthe reactor and the other half of the reactor is used to produce power.
  • the control grid is placed in the center of the core and safety plates 37 are inserted into the reactor.
  • control grid 33 affords a convenient means of reducing this neutron loss. Since Pa has a half-life of 27 days, the amount present will be reduced significantly by allowing a reactor to sit for 27 days after operation. Thus the control grid may be placed at the top of the reactor for 27 days while power is obtained from the bottom half of the reactor. The control grid is then moved to the bottom half of the reactor for 27 days to permit power to be obtained from the top half. While the bottom half is shut down, half of the Pa present decays to form U so that when the control grid is moved again the amount of Pa present is significantly reduced.
  • the amount of fuel necessary to obtain criticality under various condition is described in report ANL-6378 dated December 1961.
  • the height of the core will be approximately twice that described and the number of fuel elements will be sufficient to obtain the desired power.
  • a nuclear reactor comprising a core consisting of a plurality of vertically disposed clusters of fuel elements immersed in heavy water, said fuel elements being composed of a major proportion of thoria and a minor proportion of enriched urania and said core being of approximately twice the height required for criticality, and a control grid of thorium of slightly greater than onehalf the height of the reactor core mounted for vertical movement within the core.
  • a nuclear reactor comprising a core, a light-Water reflector surrounding the core, a control grid of thorium mounted for vertical movement within the core, and a pair of safety rods mounted for rapid insertion'into the core, said core comprising a plurality of vertically disposed clusters of fuel elements composed of a major proportion of thoria and a minor proportion of enriched urania disposed within Vertically disposed pressure tubes, means for passing heavy water under pressure through the pressure tubes, and a mass of heavy water surrounding the pressure tubes, characterized by said core being approximately twice the height required for criticality and said control grid being slightly greater than one-half the height of the core.
  • a method of operating a ura-nia-thoria, heavy-water power reactor which is approximately twice the height required for criticality comprising adjusting a thorium control grid so that one-half of the reactor is critical while the other half is not critical, operating the reactor for approximately 27 days, moving the thorium control grid to shut down the originally critical half of the reactor and make the other critical, again operating for 27 days, and repeating the procedure as long as criticality is attained.
  • a heavy-water, urania-thoria power reactor incorporating a control grid of thorium, the improvement comprising the reactor core being of twice the height required for criticality and the control grid of thorium being slightly greater than half the height of the reactor core.

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  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Chemical & Material Sciences (AREA)
  • Chemical Kinetics & Catalysis (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)

Description

Dec. 22, 1964 Filed Nov. 6, 1963 w. c. REDMAN 3,162,577
REAQTOR CONTROL WITH THORIUM CONTROL. GRID 2 Sheets-Sheet 1 INVENTOR 26' llltltaam 'fedmafi .Z'Zzfarzzgy Dec. 22, 1964 w. c. REDMAN REACTOR CONTROL WITH THORIUM CONTROL GRID 2 Sheets-Sheet 2 Filed Nov. 6, 1963 INVENTOR. 111,204; 6,26
BY M 4..
3,162,577 REACTUR CQNTROL WITH THQRIUM C(PNTRQL GRHD William C. Redman, Hinsdale, ilk, assignor to the United States of America as represented by the United States Atomic Energy Commission lFiled Nov. 6, 1963, Ser. No. 321,984 4 Claims. (Cl. 17621) This invention relates to a nuclear reactor and particularly to a urania-thoria power reactor wherein heavy water serves as moderator. The invention also relates to novel means for controlling such a reactor to enhance the neutron economy and extend the useful life of the reactor. The invention further relates to a method of operating such a reactor.
Power reactors are always constructed with an appreciable excess reactivity to extend the lifetime .of the reactor. It is customary to use burnable poisons or shim control rods to compensate for this initial excess reactivity. As the fuel in the reactor burns out, the burnable poison burns out and/ or the shim rods are withdrawn to increase the available reactivity. Both of these expedients succeed in extending the reactivity lifetime of a reactor but both adversely affect the neutron economy in the reactor due to nonproductive loss of neutrons in the burnable poison and the shim rods.
The thoria-urania system is very attractive for power reactors because of the abundance ofthoria, the high burnup potentially attainable in a thoria-urania reactor, and the compatibility of thoria and urania with hightemperature water. Similarly, heavy water is attractive as a moderator in a thoria-urania reactor because of the good neutron economy attainable therewith. Unfortu nately, above a power level of a few megawatts per kilogram of fissionable material, neutron economy is impaired significantly by the large capture cross section of 27-day Pa which is an intermediate product in the transmutation of Th to U as shown by the following nuclear equations:
Th +n Th +'y 233 2s3+ 233 233+ It is accordingly an object of the present invention to develop a nuclear reactor having improved neutron economy and increased core lifetime.
It is a more detailed object of the present invention to mitigate the effect of Pa on the neutron economy of a urania-thoria reactor.
It is also an object of the present invention to develop a method of operating a urania-thoria reactor to obtain an increased lifetime.
These and other objects of the present invention are attained in a urania-thoria reactor which is approximately twice the height required by nuclear design considerations and which includes a movable control grid of thorium slightly greater than one-half the height of the reactor. The control grid is employed for ordinary control of the reactor, thereby enhancing the neutron economy of the reactor since a useful product is formed in the control grid. The control grid also makes it possible to mitigate the effect of Pa on the neutron economy of the reactor. By shifting the reactive part of the reactor from the top half of the reactor to the bottom half of the reactor or vice versa every 27 days with the control grid, half of the Pa decays of U before the portion of the reactor in which it is present again becomes chain reactive.
The invention will next be described in connection with the accompanying drawings wherein FIG. 1 is a diagrammatic cross-section of a nuclear reactor illustrating the present invention,
v a control grid 33 of thorium which is raised and lowered 3,162,577 Patented Dec. 22, 1964 FIG. 2 is a horizontal cross-section thereof taken on the line 22,
FIG. 3 is a perspective view of a control grid which is of primary importance to the present invention, and
FIG. 4 is a horizontal cross-section of a typical fuel element.
As shown in the drawing, the reactor comprises a core 1 0 and a reflector 11 surrounding the core. Core 10 and reflector 11 are separated by an inner shell 12 while an outer shell 13 encloses the entire reactor. Reflector 11 extends the full length of the core between an upper plate 14 at the top of inner shell 12 and a lower plate 15 at the bottom of inner shell 12 and light water is introduced thereinto through inlet 16 and withdrawn through outlet 17.
Core 10 is composed of bundles of parallel fuel rods 18 (see FIG. 4) disposed in a plurality of vertical pressure tubes 19. Spiral wires 20 on the fuel rods 18 assure that the fuel rods are properly spaced. Fuel rods 18 are supported by clamps (notshown) at the top and bottom of the pressure tubes 19.
Pressure tubes 19 extend between a lower support grid 21 disposed at the bottom of inner shell 12 and an upper guide grid 22 disposed intermediate of inner shell 12 and above the top of core 10. An annular inlet header 23 is disposed below the core while an annular outlet header 24 is disposed above the core. Lower pressure tube extensions 25 and inlet ducts 26 provide communication between inlet header 23 and pressure tubes 19 while upper pressure tube extensions 27 and outlet ducts 28 provide communication. between outlet header 24 and pressure tubes 19.
Fuel rods 18 consist of fired pellets of a uniform mix- 1 ture of highly enriched urania and thoria in a tube formed I of a corrosion-resistant material of low neutron capture cross-section such as Ziroaloy-II.
The primary coolant flow through the reactor passes through pressure tubes 19. Heavy water under pressure enters pressure tubes 19 from ducts 26 and header 23 and is there heated by fuel rods 18. The heated heavy water is withdrawn through outlet ducts 28 and outlet header 24 to produce power exterior to the reactor.'
Inner shell 12 contains a body of heavy Water 29 which serves asmoderator and secondary coolant. A continuous flow of heavy water is maintained by introducing heavy water into reactor vessel 13 below the core through moderator inlet 3d and withdrawing it from reactor vessel 13 above the core through moderator outlet 31. The heavy water passes into and out of inner shell 12 through perforations 32 (see FIG. 2) in support grid 21 and guide grid 22. t
. Primary control of the reactor is obtained by means of by means of cables 34. As shown in FIG. 3, control grid 33 comprises an outer box55 which is open at both ends and intersecting sheets 36 of thorium in the box 35. The sheets of thorium are spaced far enough apart to clear pressure tubes 19 so that the control grid 33 interpenetrates the reactor core 10. The thorium employed to form control grid 33 is, of course, clad in a corrosionresistant material such as Zircaloy-II. In addition to control grid 33, control plates 37 operated by cables 38 are provided for safety control.
7 The primary point of novelty according to the present invention resides in the use of a control grid 33 of slightly greater than one-half the height of the core in a reactor core'which is twice the height required by design considerations for criticality. Thus only half of the core is required for operation of the reactor. The thorium grid is placed so as to prevent a chain reaction in either the top half or the bottom half ofthe reactor and the other half of the reactor is used to produce power. To shut 3 down the reactor, the control grid is placed in the center of the core and safety plates 37 are inserted into the reactor.
As pointed out heretofore, the large capture crosssection of Pa which is an intermediate product in the transmutation of Th to U impairs neutron economy significantly in a power reactor. Control grid 33 affords a convenient means of reducing this neutron loss. Since Pa has a half-life of 27 days, the amount present will be reduced significantly by allowing a reactor to sit for 27 days after operation. Thus the control grid may be placed at the top of the reactor for 27 days while power is obtained from the bottom half of the reactor. The control grid is then moved to the bottom half of the reactor for 27 days to permit power to be obtained from the top half. While the bottom half is shut down, half of the Pa present decays to form U so that when the control grid is moved again the amount of Pa present is significantly reduced.
Using the herein-described fuel, the amount of fuel necessary to obtain criticality under various condition is described in report ANL-6378 dated December 1961. According to the present invention the height of the core will be approximately twice that described and the number of fuel elements will be sufficient to obtain the desired power.
It will be understood that the invention is not to be limited to the details given herein but that it may be modified within the scope of the appended claims.
The embodiments of the invention in which an exclusive property or privilege is claimed are defined as follows:
1. A nuclear reactor comprising a core consisting of a plurality of vertically disposed clusters of fuel elements immersed in heavy water, said fuel elements being composed of a major proportion of thoria and a minor proportion of enriched urania and said core being of approximately twice the height required for criticality, and a control grid of thorium of slightly greater than onehalf the height of the reactor core mounted for vertical movement within the core.
2. A nuclear reactor comprising a core, a light-Water reflector surrounding the core, a control grid of thorium mounted for vertical movement within the core, and a pair of safety rods mounted for rapid insertion'into the core, said core comprising a plurality of vertically disposed clusters of fuel elements composed of a major proportion of thoria and a minor proportion of enriched urania disposed within Vertically disposed pressure tubes, means for passing heavy water under pressure through the pressure tubes, and a mass of heavy water surrounding the pressure tubes, characterized by said core being approximately twice the height required for criticality and said control grid being slightly greater than one-half the height of the core.
3. A method of operating a ura-nia-thoria, heavy-water power reactor which is approximately twice the height required for criticality comprising adjusting a thorium control grid so that one-half of the reactor is critical while the other half is not critical, operating the reactor for approximately 27 days, moving the thorium control grid to shut down the originally critical half of the reactor and make the other critical, again operating for 27 days, and repeating the procedure as long as criticality is attained.
4. In a heavy-water, urania-thoria power reactor incorporating a control grid of thorium, the improvement comprising the reactor core being of twice the height required for criticality and the control grid of thorium being slightly greater than half the height of the reactor core.
References Cited by the Examiner UNITED STATES PATENTS 2,840,522 6/58 Young et a1 176-21 FOREIGN PATENTS 657,633 2/63 Canada.
OTHER REFERENCES ANL-6378, publ. by ABC, p. 13, December 1961.
CARL D. QUARFORTH, Primary Examiner.

Claims (2)

1. A NUCLEAR REACTOR COMPRISING A CORE CONSISTING OF A PLURALITY OF VERTICALLY DISPOSED CLUSTERS OF FUEL ELEMENTS IMMERSED IN HEAVY WATER, SAID FUEL ELEMENTS BEING COMPOSED OF A MAJOR PORPORTION OF THORIA AND A MINOR PROPORTION OF ENRICHED URANIA AND SAID CORE BEIING OF APPROXIMATELY TWICE THE HEIGHT REQUIRED FOR CRITICALITY, AND A CONTROL GRID OF THORIUM OF SLIGHTLY GREATER THAN ONEHALF THE HEIGHT OF THE REACTOR CORE MOUNTED FOR VERTICAL MOVEMENT WITHIN THE CORE.
3. A METHOD OF OPERATING A URANIA-THORIA, HEAVY-WATER POWER REACTOR WHICH IS APPROXIMATELY TWICE THE HEIGHT REQUIRED FOR CRITICALITY COMPRISING ADJUSTING A THORIUM CONTROL GRID SO THAT ONE-HALF OF THE REACTOR IS CRITICAL WHILE THE OTHER HALF IS NOT CRITICAL, OPERATING THE REACTOR FOR APPROXIMATELY 27 DAYS, MOVING THE THORIUM CONTROL GRID TO SHUT DOWN THE ORIGINALLY CRITICAL HALF OF THE REACTOR AND MAKE THE OTHER CRITICAL, AGAIN OPERATING FOR 27 DAYS, AND REPEATING THE PROCEDURE AS LONG AS CRITICALITY IS ATTAINED.
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Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3410340A (en) * 1965-06-02 1968-11-12 Kernforschungsanlage Juelich Liquid-fuel nuclear-reactor-core walland-channel structure
ITPI20110046A1 (en) * 2011-04-26 2012-10-27 Chellini Fabio METHOD AND SYSTEM TO GENERATE ENERGY BY MEANS OF NUCLEAR REACTIONS OF HYDROGEN ADSORBED BY ORBITAL CATCH FROM A CRYSTALLINE NANOSTRUCTURE OF A METAL

Citations (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US2840522A (en) * 1945-09-18 1958-06-24 Gale J Young Reactor and novel method
CA657633A (en) * 1963-02-12 R. Blake Leslie Controlling of nuclear reactors

Patent Citations (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CA657633A (en) * 1963-02-12 R. Blake Leslie Controlling of nuclear reactors
US2840522A (en) * 1945-09-18 1958-06-24 Gale J Young Reactor and novel method

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3410340A (en) * 1965-06-02 1968-11-12 Kernforschungsanlage Juelich Liquid-fuel nuclear-reactor-core walland-channel structure
ITPI20110046A1 (en) * 2011-04-26 2012-10-27 Chellini Fabio METHOD AND SYSTEM TO GENERATE ENERGY BY MEANS OF NUCLEAR REACTIONS OF HYDROGEN ADSORBED BY ORBITAL CATCH FROM A CRYSTALLINE NANOSTRUCTURE OF A METAL
WO2012147045A1 (en) * 2011-04-26 2012-11-01 Piantelli, Silvia Method and apparatus for generating energy by nuclear reactions of hydrogen adsorbed by orbital capture on a nanocrystalline structure of a metal

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